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Event Notification Report for September 20, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/19/2013 - 09/20/2013

** EVENT NUMBERS **


49334 49338 49340 49356 49357 49358 49359 49361 49362 49363

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Power Reactor Event Number: 49334
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JEREMEY COBBS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/09/2013
Notification Time: 16:05 [ET]
Event Date: 09/09/2013
Event Time: 13:00 [PDT]
Last Update Date: 09/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL HAY (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

PLANNED PARTIAL LOSS OF COMMUNICATIONS CAPABILITY IN TECHNICAL SUPPORT CENTER

"This is a non-emergency eight hour notification for a planned loss of communications capability at the DCPP Technical Support Center (TSC). This event is reportable in accordance with 10CFR50.72(b)(3)(xiii) because planned maintenance affects the functionality of some TSC communications systems.

"Planned maintenance activities on the TSC communications systems begins 09/09/13. The work includes removing phones and normal business use computers from service to support a minor remodel which includes the installation of new furniture and painting in the TSC command room. The communications equipment scope of work is confined to the TSC command room only and there is no expected loss of capability in the engineering, administrative or radiological rooms within the TSC. There is no expected loss of plant display systems (SPDS, ERDS, or ERFDS) in the TSC during this planned maintenance. The work is scheduled to complete by 09/26/2013.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. A select group of TSC ERO personnel have been pre-designated to respond to their backup TSC location in accordance with applicable site procedures. If a complete relocation of the TSC becomes necessary, the Site Emergency Coordinator will relocate the remaining TSC staff to a backup location in accordance with applicable site procedures. The Emergency Response Organization teams have been notified of the planned maintenance and the possible need to relocate during an emergency.

"The NRC Resident Inspector has been notified. This planned maintenance poses no threat to the public or station employees."

* * * UPDATE FROM ADAM PECK TO HOWIE CROUCH AT 1704 EDT ON 9/19/13 * * *

"The planned maintenance on the TSC communications systems is complete. DCPP restored the emergency response communications capability at 1400 PDT on September 19, 2013."

The licensee has notified the NRC Resident Inspector.

Notified R4DO (Deese).

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Agreement State Event Number: 49338
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: FROEHLING & ROBERTSON
Region: 1
City: SUTHERLAND State: VA
County: DINWIDDIE
License #: VA-760-096-02
Agreement: Y
Docket:
NRC Notified By: MICHAEL WELLING
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/11/2013
Notification Time: 17:24 [ET]
Event Date: 09/11/2013
Event Time: [EDT]
Last Update Date: 09/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
FSME EVENTS RESOURCE (E-MA)
ILTAB (E-MA)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE

The following information was received via facsimile:

"A Troxler model 3411 gauge was stolen from the licensee's truck while at a temporary jobsite. The authorized user placed the gauge in the back of the truck and stepped away to perform other work. When he returned, he found the gauge was gone. He contacted his RSO. The Dinwiddie Sheriff's office was notified and a report filed. The licensee searched the near area but did not find the gauge.

"A press release is being issued by VDH [Virginia Department of Health] utilizing the Richmond and Petersburg area media outlets."

Virginia Report Number: VA-13-08

* * * UPDATE FROM MIKE WELLING TO JOHN SHOEMAKER AT 1605 EDT ON 9/12/13 * * *

"On September 12, 2013, a member of the public returned the gauge to a local business who then contacted the local authorities. The [Virginia] RMP (Radiation Materials Program) was notified and a staff member was dispatched to ascertain the gauge condition. A survey was performed and all readings were found to be within expected dose rates. A wipe test of the gauge was performed and no contamination was found. The licensee was notified and arrived on scene. The gauge was returned to the licensee and an observation was made of the gauge being blocked and braced and secured with cables in the vehicle. An investigation is being performed by RMP."

Notified R1DO (Cahill), FSME Events Resource (via email), and ILTAB (via email).

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Agreement State Event Number: 49340
Rep Org: COLORADO DEPT OF HEALTH
Licensee: BAKER HUGHES
Region: 4
City: BRIGHTON State: CO
County:
License #: CO RML#678-01
Agreement: Y
Docket:
NRC Notified By: CHERI HALL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/12/2013
Notification Time: 20:17 [ET]
Event Date: 08/13/2013
Event Time: [MDT]
Last Update Date: 09/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE - SCRAP METAL SHIPMENT CONTAINING RADIOACTIVE MATERIAL

The following information was received via facsimile:

"On August 13, 2013, the Colorado State Department Public Health and Environment received a phone call from Western Metals Recycling indicating a need for a special permit to return a shipment of scrap metal flagged as containing radioactive materials by portal monitor alarms. The shipment originated at Baker Hughes of Brighton, Colorado (CO RML#678-01). The DOT Special Permit (#CO-CO-13-01) was issued on August 13, 2013, with a reading of 0.04 mrem/hr on the outside of the shipment.

"On August 15, 2013, the rolloff was returned to Baker Hughes, where they determined a number of valves and seats from a fluid end of a well fracking site contained the contamination. The Baker Hughes staff tracked the parts back to a site worked in conjunction with ProTechnics (CO RML#545-01) with radioactive tracer material. ProTechnics was contacted and offered to take possession of the material. Baker Hughes reported valves with readings ranging from 0.02 mrem/hr to 1 mrem/hr on contact.

"On August 19, 2013, the Colorado State Department Public Health and Environment's Health Physicists visited the Brighton location of Baker Hughes, where the material was being held, to meet with staff from both Baker Hughes and ProTechnics. The material was identified as Ir-192, using an Identifinder 2 detector, with a dose rate of 0.2 mrem/hr on contact with one of the valves. It was decided ProTechnics would take possession of all parts contaminated with radioactive material in order to decontaminate and store the waste for decay. An amendment or provisional license was necessary for either Western Metals Recycling or Baker Hughes.

"On August 26, 2013, the Colorado State Department Public Health and Environment received the survey reports from the Thompsen well site for the dates of concern. The survey reports showed no contamination was detected

"On August 30, 2013, the Colorado State Department Public Health and Environment received a full report from Protechnics indicating approximately 0.026 mCi of Ir-192 was recovered from the contaminated equipment and will be held for decay at their Fruita facilities.

"A Notice of Violation will be issued in response to this event."

Colorado State Incident Report I13-09.

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Power Reactor Event Number: 49356
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT. IHLENFELDT
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/19/2013
Notification Time: 03:10 [ET]
Event Date: 09/18/2013
Event Time: 22:29 [CDT]
Last Update Date: 09/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KENNETH RIEMER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

BOTH SECONDARY CONTAINMENT ACCESS DOORS BRIEFLY OPENED SIMULTANEOUSLY

"While performing the secondary containment airlock door interlock surveillance, the interlock to the main plenum room did not prevent the opening of both doors to the plenum room airlock (DOOR-85 and DOOR-86). The plenum room airlock doors were immediately closed. The time both doors were opened is estimated to be approximately one (1) second.

"When both doors open, Technical Specification surveillance requirement SR 3.6.4.1.3 was not met and secondary containment was declared inoperable. Secondary containment was declared operable after independently verifying at least one secondary containment access door was closed.

"There were no radiological releases associated with this event. The NRC resident inspector has been notified."

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Power Reactor Event Number: 49357
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: NATHAN PIEPER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/19/2013
Notification Time: 09:58 [ET]
Event Date: 09/19/2013
Event Time: 04:50 [CDT]
Last Update Date: 09/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
KENNETH RIEMER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER EMERGENCY DIESEL GENERATOR REMOVED FROM SERVICE FOR PLANNED MAINTENANCE

"A planned maintenance evolution at the Duane Arnold Energy Center (DAEC) will remove the emergency power supply to the TSC from service. The TSC would be rendered non-functional with the loss of emergency power. The repair to the power supply is expected to last 2 hours.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. Maintenance will be expedited to restore the emergency power supply to service.

"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the loss of an Emergency Response Facility (ERF). An update will be provided once the TSC emergency power supply has been restored to normal operation.

"NRC resident has been notified."

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Power Reactor Event Number: 49358
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BENJAMIN AGNEW
HQ OPS Officer: CHARLES TEAL
Notification Date: 09/19/2013
Notification Time: 13:17 [ET]
Event Date: 07/23/2013
Event Time: [EDT]
Last Update Date: 09/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
DON JACKSON (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 3 ACTUATION

"This notification is being made in accordance with 10CFR50.73 (a)(2)(iv)(A) to provide information pertaining to an invalid Primary Containment Isolation System (PCIS) Group 3 actuation signal that affected containment valves in more than one system.

"On 7/23/2013, and again on 7/24/2013, with the reactor at 100% power, an invalid PCIS Group 3 actuation occurred from a momentary spike of the 'B' Reactor Building ventilation radiation monitor which reached the instrument's high radiation trip set point. A radiation protection technician was dispatched and radiation levels in the vicinity of the 'B' radiation monitor were verified to be normal and below the alarm set points. The radiation monitor was verified to be indicating normal expected radiation levels. Subsequent visual inspection and functional checks of the radiation monitors were completed satisfactory and the instrument channel was returned to service.

"At the recommendation from the vendor, the detectors were replaced in both of the Reactor Building ventilation monitors as well as the Refuel Floor radiation monitors.

"On 8/19/2013, 9/12/2013, and 9/13/2013, with the reactor at 100% power, invalid PCIS Group 3 actuations occurred from a momentary spike of the 'A' Refuel Floor radiation monitor which reached the instrument's high radiation trip set point. A radiation protection technician was dispatched to the refuel floor and dose rates in the vicinity of the 'A' radiation monitor detector were verified to be normal and below the alarm set points. The radiation monitor was verified to be indicating normal expected radiation levels. Subsequent visual inspection and functional checks of the radiation monitors were completed satisfactory and the instrument channel was returned to service.

"Both trains of Standby Gas Treatment System started as designed and Reactor Building ventilation isolated as a result of the invalid PCIS actuation.

"The PCIS functioned successfully providing a complete Group 3 isolation. The PCIS Group 3 isolation involves the following systems:

Drywell and Suppression Chamber air and vent: V16-19-6A, 6B, 7, 7A, 7B, 8, 9, 10, 23
Containment Makeup: V-16-20-20, 22A, 22B
Containment Air Sampling: VG-23, 26, V109-76A, 76B
Containment Air compressor suction: V72-38A, 38B
Containment Air Dilution: VG-9A, 9B, 22A, 22B, NG-11A, 11B, 12A, 12B, 13A, 13B

"Since no actual high radiation condition existed which required the PCIS Group 3 isolation, and the actuation was not in response to actual plant conditions satisfying the requirements for isolation, this event has been classified as an invalid actuation.

"This event did not result in any adverse impact to the health and safety of the public."

"In accordance with 10CFR50.73(a)(1) a telephone notification is being made instead of submitting a written Licensee Event Report. The licensee has notified the NRC resident inspector."

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General Information Event Number: 49359
Rep Org: DUKE ENERGY
Licensee: DUKE ENERGY
Region: 1
City: CHARLOTTE State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JULIE OLIVIER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/19/2013
Notification Time: 14:32 [ET]
Event Date: 09/18/2013
Event Time: 16:45 [EDT]
Last Update Date: 09/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
DEBORAH SEYMOUR (R2DO)

Event Text

APPARENT FALSE NEGATIVE INDICATED ON A BLIND PERFORMANCE TEST

"Per 10 CFR 26.719 section (c)(3), Duke Energy is making this notification of an apparent false negative error that has occurred on a blind performance test sample submitted to the Health and Human Services (HHS)-certified laboratory used for drug testing. On September 18, 2013, Duke Energy was notified that a drug sample that was part of a blind performance test package provided by El Solhy and submitted to LabCorp tested negative. Duke Energy will investigate the issue and report to the NRC as required by part 26.719(c)(1). El Solhy and LabCorp are contracted by Duke Energy as required by NRC regulations to provide fitness for duty services. Duke Energy has notified the NRC Branch Chief for the Fitness for Duty program [Paul Harris], which advised that Duke needs to notify the NRC Headquarters Operations Center."

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Power Reactor Event Number: 49361
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: STEPHEN SEILHYMER
HQ OPS Officer: CHARLES TEAL
Notification Date: 09/19/2013
Notification Time: 17:13 [ET]
Event Date: 09/19/2013
Event Time: 12:20 [CDT]
Last Update Date: 09/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
KENNETH RIEMER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 80 Power Operation 80 Power Operation

Event Text

NO DOCUMENTED PLAN IN PLACE TO RECEIVE ADDITIONAL FUEL OIL DURING MAXIMUM PROBABLE FLOOD CONDITION

"On September 19, 2013, a potential unanalyzed condition was identified. The current licensing basis requires a 14 day supply of fuel oil. Preliminary calculations show that there is sufficient tank volume for the duration of design basis maximum probable flood condition. However, during maximum flood condition there is currently no documented plan in place to receive additional fuel oil to maintain Unit 1 and Unit 2 Emergency Diesel Generators operable and running to supply emergency power to essential loads for the duration of the effects of a design basis maximum probable flood condition. These effects, such as flooded roads, may exceed 14 days. This is not an immediate safety concern because additional fuel oil can be added to the fuel oil storage tanks for imminent flood conditions.

"The NRC Resident has been notified."

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Power Reactor Event Number: 49362
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DANIEL PIPKIN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 09/19/2013
Notification Time: 20:31 [ET]
Event Date: 09/19/2013
Event Time: 14:37 [CDT]
Last Update Date: 09/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RICK DEESE (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

SECONDARY CONTAINMENT INOPERABLE DUE TO AN UNATTENDED OPEN DOOR

"Security personnel reported to the Main Control Room that at time 1437 CDT, an alarm indicated that a secondary containment door was open beyond the normal delay time allowed for entry and exit. Security personnel responded and found the door open and unattended with the dogs extended meaning that the door was unable to be closed. Security personnel secured the door at time 1441 CDT. No deficiencies were found with the door. The fact that the door was open and unattended beyond the time allowed for normal entry and exit violates Technical Specification 3.6.4.1, 'Secondary Containment- Operating,' because surveillance requirement SR 3.6.4.1.3 was not met. This surveillance requires that doors be closed except during normal entry and exit.

"In summary, an SSC was inoperable in a required mode as a result of a personnel error and no redundant equipment in the same system was operable. Thus, the condition is reportable under 10CFR50.72(b)(3)(v)(D)."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 49363
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT IHLENFELDT
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/19/2013
Notification Time: 23:56 [ET]
Event Date: 09/19/2013
Event Time: 17:50 [CDT]
Last Update Date: 09/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KENNETH RIEMER (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

HIGH PRESSURE COOLANT INJECTION INOPERABLE DUE TO STEAM LEAK

"On 9/19/2013, during the performance of the High Pressure Coolant Injection (HPCI) quarterly pump and valve surveillance, a steam leak was discovered. HPCI had previously been declared inoperable due to planned maintenance. As a result of the steam leak, HPCI remains inoperable.

"Action taken: 14 days Required Action TS 3.5.1.J.2 remains in effect and corrective actions are in progress.

"The licensee has notified the NRC Resident Inspector."

Page Last Reviewed/Updated Friday, September 20, 2013
Friday, September 20, 2013